Published 2000
| Version v1
Computer medium
Solutions of system of P1 equations without use of auxiliary differential equations coupled
- 1. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear
Description
The system of P1 equations is composed by two equations coupled itself one for the neutron flux and other for the current. Usually this system is solved by definitions of two integrals parameters, which are named slowing down densities of the flux and the current. Hence, the system P1 can be change from integral to only two differential equations. However, there are two new differentials equations that may be solved with the initial system. The present work analyzes this procedure and studies a method, which solve the P1 equations directly, without definitions of slowing down densities. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Solucoes do sistema de equacoes P1 sem o uso de equacoes diferenciais auxiliares acopladas
Publishing Information
- Imprint Title
- Nuclear future: thinking for building. Proceedings of the 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [800 p.]
- Journal Page Range
- p. 600-605
Conference
- Title
- 12. Brazilian national meeting on reactor physics and thermal hydraulics; 8. General congress on nuclear energy; 5. Brazilian national meeting on nuclear applications
- Original Conference Title
- 12. Encontro nacional de fisica de reatores e termo-hidraulica
- Dates
- 5-20 Oct 2000
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 32022808
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- INTEGRO-DIFFERENTIAL EQUATIONS; NEUTRON DENSITY; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NUMERICAL SOLUTION; P1-APPROXIMATION; SPATIAL DISTRIBUTION
- Descriptors DEC
- CALCULATION METHODS; DISTRIBUTION; EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; SPHERICAL HARMONICS METHOD; TRANSPORT THEORY
Optional Information
- Notes
- 3 refs., 1 graph Imprint:Published only in CD-Rom. Available from the Library of the Brazilian Nuclear Energy Commission, Rio de Janeiro;Futuro nuclear: refletindo para construir. Anais do 12. Encontro nacional de fisica de reatores e termo-hidraulica; 8. Congresso geral de energia nuclear; 5. Encontro nacional de aplicacoes nucleares